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Title: Aluminum-uranium fuel-melt behavior during severe nuclear reactor accidents

Journal Article · · Nuclear Safety; (United States)
OSTI ID:6989880
 [1]; ; ; ;  [2];  [3]
  1. Idaho National Engineering Lab., Idaho Falls, ID (United States)
  2. Westinghouse Savannah River Lab., Aiken, SC (United States)
  3. Fauske and Associates, Burr Ridge, IL (United States)

The behavior of aluminum-uranium alloy nuclear reactor fuels in severe melting accidents is assessed. The results from several in-pile overheating incidents and from several experimental tests are used to derive conclusions regarding melt behavior and fission-product release in severe reactor accidents. These assessments indicate three distinct stages of fuel failure, which are described in detail. Experimental results that illustrate the foaming behavior of irradiated metallic fuels are also presented. These data describe the importance of the oxide film on the surface of the molten fuel in determining the fuel relocation behavior. The foaming and swelling of the fuel also are shown to correlate with the fission-product release phenomena. 59 refs., 1 tab.

DOE Contract Number:
AC07-76ID01570; AC09-89SR18035
OSTI ID:
6989880
Journal Information:
Nuclear Safety; (United States), Vol. 34:2; ISSN 0029-5604
Country of Publication:
United States
Language:
English